L-13-009, Response to NRC Letter Dated May 20. 2013, Diablo Canyon Power Plant Independent Spent Fuel Installation Storage Inspection Report 05000275-13-008, 05000323-13-008, 07200026-13-001 of Notice of Violation
DCL-12-126, Response to NRC Letter Dated November 13, 2012, Diablo Canyon Power Plant - NRC Integrated Inspection Report 05000275-12-004 and 05000323-12-004
DCL-15-130, Response to NRC Request for Additional Information Regarding License Amendment Request 15-03, Application of Alternative Source Term
DCL-15-136, Response to Requests for Information Related to the Environmental Review of the License Renewal Application - Severe Accident Mitigation Alternatives
DCL-15-125, Response to NRC Request for Additional Information Regarding License Amendment Request 15-03, Application of Alternative Source Term
DCL-15-121, Responds to NRC Letter Dated September 24, 2015, Request for Additional Information for the Review of the License Renewal Application - Set 38
DCL-15-118, Response to NRC Request for Additional Information Regarding Relief Request FLIG-U1
DCL-15-111, Response to NRC Request for Additional Information Dated August 27, 2015, Regarding Recommendation 2.1 of the Near-Term Task Force Seismic Hazard and Screening Report
DCL-15-106, ASME Section XI Inservice Inspection Program Request for Relief NDE-FWNS-U1/U2 to Allow Use of Alternate Examination Volume Coverage Requirements
DCL-15-099, Fifth Six-Month Status Report in Response to March 12. 2012. Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)
DCL-15-101, ASME Section XI Inservice Inspection Program Request for Relief NDE-SG-MS-IR, Main Steam Nozzle Inner Radius Examination Impracticality
DCL-15-091, Submits License Amendment Request Exigent Revision to Technical Specification 3.8.9. Distribution Systems - Operating
DCL-15-095, Response to NRC Request for Additional Information Regarding Recommendation 2.1 of the Near-Term Task Force Seismic Hazard and Screening Report
DCL-15-093, 10 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for Peak Cladding Temperature for 2014
DCL-15-087, Revision to TS 3.4.15 for License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-432, Revision 1, Change in Technical Specification End States (WCAP-16294)
DCL-15-086, ASME Section XI Inservice Inspection Program Request for Relief PRS-3
DCL-15-080, License Renewal Severe Accident Mitigation Alternatives Analysis Evaluation of the 2015 Seismic Hazard Results
DCL-15-079, Revision to Regulatory Commitment- Generator Circuit Breakers License Amendment Request, Commitment Withdrawal
DCL-15-073, Independent Spent Fuel Storage Installation Revision 11 of the Physical Security Plan
DCL-15-072, Revisions to Supplement for License Amendment Request 11-07, Process Protection System Replacement
DCL-15-075, Relief Request REP-SI - Supplement
DCL-15-061, Second Radiation Release Response to NRC Request for Additional Information - National Fire Protection Association Standard 805
DCL-15-054, One Hundred Eighty-Day Steam Generator Report for Diablo Canyon Power Plant, Unit 2, Eighteenth Refueling Outage
DCL-15-042, Supplemental Licensee Event Report 1-2014-004-01 for Diablo Canyon, Units 1 and 2 Regarding Actuation of Six Emergency Diesel Generators Due to Loss of Offsite Power
DCL-15-041, Supplemental LER 2-13-004-01 for Diablo Canyon, Unit 2 Regarding Technical Specification 3.8.1 Not Met Due to Failed Wire Lug on Emergency Diesel Generator 2-3
DCL-15-040, Response to NRC Request for Additional Information Regarding Unit 1 Reactor Vessel Inspection Interval Extension from 10 to 20 Years
DCL-15-038, Response to NRC Request for Additional Information Regarding Relief Request REP-SI - Part 2
DCL-15-009, Submittal of Advanced Logic System Phase 2 Documents for the License Amendment Request for Digital Process Protection System Replacement
DCL-15-032, Response to NRC Request for Additional Information - National Fire Protection Association Standard 805
DCL-15-031, Proposed Commitment for Response to NRC Request for Additional Information Regarding Submittal Date of the Integrated Analysis, National Fire Protection Association Standard 805
DCL-15-028, Fourth Six-Month Status Report in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)
DCL-15-026, Fourth Six-Month Status Report in Response to March 12, 2012, Commsission Order Modifying Licesnes with Regard to Requirements for Mititgstion Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)
DCL-15-025, Supplement to License Amendment Request 14-05 for Revision to the Cyber Security Plan Implementation Schedule Completion Date
DCL-14-123, Radiation Release Response to NRC Request for Additional Information- National Fire Protection Association Standard 805
DCL-14-121, Cancellation of Licensee Event Report 1-2014-001
DCL-14-107, Licensing Basis Verification Project Change in Commitment Regarding Component Design Basis Reviews
DCL-14-100, Expected Submittal Date for Licensee Event Report 1-2014-003 Supplement 2
DCL-14-093, Revision to Response Date for NRC Request for Additional Information - Fire Modeling 3 - National Fire Protection Association Standard 805
DCL-14-077, Third Six-Month Status Report in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number (EA-12-051)
DCL-14-076, Third Six-Month Status Report in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)
DCL-14-074, ASME Section XI Inservice Inspection Program Request for Alternative RPV-U1-Extension to Allow Use of Alternate Reactor Reactor Inspection Interval Requirements
DCL-14-073, Request Waiver Fee as Pilot Plant for Simplified Risk-Informed Approach for Closure of GSI-191
DCL-14-072, Unit 2 - Relief Request NDE-SFW-13: Correction to the List of Docket Numbers
DCL-14-070, CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for Peak Cladding Temperature for 2013
DCL-14-068, Response to NRC Request for Additional Information Regarding Relief Request SWOL-REP-1 U2
DCL-14-058, License Amendment Request 14-03 for Adoption of Technical Specification Task Force Traveler TSTF-432, Revision 1. Change in Technical Specification End States (WCAP-16294)
DCL-14-067, Revision to Regulatory Commitment- Generator Circuit Breakers License Amendment Request Submittal Date
DCL-14-056, 2013 Annual Commitment Change Summary Report
DCL-14-039, Annual Radioactive Effluent Release Report
DCL-14-045, Response to NRC Request for Additional Information Regarding Bequest for Preemption Authority
DCL-14-041, Response Update to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.3 Seismic
DCL-14-032, Annual Radiological Environmental Operating Report
DCL-14-036, Response to Request for Additional Information on License Amendment Request for Digital Process Protection System Replacement
DCL-14-038, Annual Nonradiological Environmental Operating Report
DCL-14-035, Updated Annual Reports of Occupational Radiation Exposure for 2008. 2009, 2010, 2011, and 2012
DCL-14-030, Diablo, Units 1 and 2 - Report of 10 CFR 50.59, Changes, Tests and Experiments, for the Period of January 1, 2012 Through December 31, 2013
DCL-14-025, Annual Report of Occupational Radiation Exposure for 2013
DCL-14-027, Request for Relief from the Requirements of Appendix IX of ASME Section XI, 2001 Edition with 2003 Addendum
DCL-14-021, Reactor Coolant System Pressure and Temperature Limits Report for Units 1 and 2
DCL-14-015, Second Six-Month Status Report in Response to March 12, 2012. Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)
DCL-14-011, Reactor Coolant System Pressure and Temperature Limits Report
DCL-13-049, Independent Spent Fuel Storage Installation Revision 8 of Physical Security Plan, Training & Qualification Plan, Safeguards Contingency Plan, & Independent Spent Fuel Storage Installation Security Program for Diablo Canyon
DCL-14-009, Response to NRC Request for Additional Information Regarding Response to NRC Bulletin 2012-01
DCL-14-007, Response to December 23, 2013, Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3 Flooding Walkdowns
DCL-13-119, Annual Update to Renewal Application and License Renewal Application Amendment Number 47
DCL-13-121, ASME Code Section XI Inservice Inspection Program Request for Alternative NDE-SFW-13 to Allow Use of Alternate Examination Requirements
DCL-13-120, Revision to Regulatory Commitment - Generator Circuit Breakers License Amendment Request Submittal Date
DCL-13-114, Response to November 1, 2013, Request for Additional Information Regarding Recommendation 2.3 Seismic
DCL-13-106, License Amendment Request 13-02 - Revision to Technical Specifications to Adopt Risk Informed Completion Times TSTF-505. Revision 1. Provide Risk-Informed Extended Completion Times-RITSTF Initiative 48
DCL-13-111, Thirty-Day Notification Report of Significant Emergency Core Cooling System Evaluation Model Changes That Affect Peak Cladding Temperature
DCL-13-103, Response to NRC Request for Additional Information Regarding Implementation of Multi-Unit/Multi-Source Dose Assessment Capability
DCL-13-091, Submittal of Revision 21 to Updated Final Safety Analysis Report
DCL-13-096, PG&E Response to NRC Request for Supplemental Information for License Amendment Request 13-03
DCL-13-095, Correction of Omissions in PG&E Letters DCL-13-018 and DCL-13-035
DCL-13-074, ISFSI - License Amendment Request 13-04, Application for U.S. NRC Authorization to Use Preemption Authority Granted Under Provisions of Section 161A of the Atomic Energy Act of 1954, as Amended
DCL-13-093, Independent Spent Fuel Storage Installation - Updates to Emergency Plan Appendices D and F
DCL-13-087, Submittal of CS Innovations Documents for the License Amendment Request for Digital Process Protection System Replacement
DCL-13-081, First Six-Month Status Report in Response to March 12, 2012. Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Event
DCL-13-078, Response to NRC Request for Additional Information Regarding Request for Relief NDE-RCS-SE-1R18 to Allow Use of Alternative Depth Sizing Criteria
DCL-13-077, CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for Peak Cladding Temperature for 2012
DCL-13-073, Response to Request for Additional Information Regarding Overall Integrated Plan in Response to March 12, 2012, Commission Order to Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order No. EA-12-051)
DCL-13-070, (DCPP) Unit 2 - ASME Section XI Inservice Inspection Program Request for Relief NDE-PNS-U2 to Allow Use of Alternate Examination Volume Coverage Requirements
DCL-13-066, Commitment for Implementation of Multi-Unit/Multi-Source Dose Assessment Capability
DCL-13-057, License Amendment Request 13-01, Administrative Revisions to Technical Specifications 3.7.10 and 5.6.5
DCL-13-058, Annual Commitment Change Summary Report
DCL-13-060, Correction of Information Provided to NRC Inspectors During the 2012 Triennial Fire Protection Inspection
DCL-13-054, Response Amendment to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.3 Seismic
DCL-13-042, Submittal of 2012 Annual Radioactive Effluent Release Report
DCL-13-048, Response to Request for Additional Information on License Amendment Request for Digital Process Protection System Replacement and Submittal of Revised PPS Replacement System Quality Assurance Plan
DCL-13-045, Annual Nonradiological Environmental Operating Report
DCL-13-029, Annual Radiological Environmental Operating Report
DCL-13-044, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident
DCL-13-040, Response to March 12.2012. NRC 10 CFR 50.54(f) Request for Information Regarding Recommendation 9.3. Phase 1 Staffing Assessment
DCL-13-038, ASME Section XI Inservice Inspection Program Relief Request NDE-RCS-SE-1R18 to Allow Use of Alternative Depth Sizing Criteria
DCL-13-025, Withdrawal of License Amendment Request 09-07, Delayed Access Offsite Power Circuit Conformance with GDC 17
DCL-13-022, Annual Report of Occupational Radiation Exposure for 2012
DCL-13-023, Reactor Coolant System Pressure and Temperature Limits Report
DCL-13-024, Supplement to ASME Section XI Inservice Inspection Program Relief Request REP-1 U2, Revision 2
DCL-13-007, Overall Integrated Plan in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)
DCL-13-011, Overall Integrated Plan in Response to March 12. 2012, Commission Order to Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)
DCL-13-012, 30-Day Response to Request for Additional Information Regarding the Recommendation 9.3 Communications Assessment
DCL-13-002, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Response to Required Response 1, Integrated Assessment Approach
DCL-12-120, Submittal of Revised Phases 1 & 2 Documents for License Amendment Request for Digital Process Protection System Replacement
DCL-12-124, 10 CFR 54.21 (B) Annual Update to the Diablo Canyon Power Plant License Renewal Application and License Renewal Application Amendment Number 46
DCL-12-129, Request for Approval of an Alternative to the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Section XI Pressure Test Requirements for Class 1 Reactor Vessel Flange Leakoff Lines
DCL-12-121, Submittal of Revised Phase 1 and 2 Documents for the License Amendment Request for Digital Process Protection System Replacement
DCL-12-117, 2011 Annual Commitment Change Summary Report
DCL-12-104, Ninety-Day Response to NRC Bulletin 2012-01: Design Vulnerability in Electric Power System.
DCL-12-102, 10 CFR 50.46 30-Day Notification Report of Significant Emergency Core Cooling System Evaluation Model Changes That Affect Peak Cladding Temperature
L-12-337, Review of the Safety Evaluation Report with Open Items Related to the License Renewal
L-12-288, Cycle 17 and Refueling Outage 17 Inservice Inspection Summary Report
L-12-335, Supplemental Reply to Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station, Unit No. 1, License Renewal Application (TAC No. ME4640) and License Renewal Application Amendment No. 34
L-12-324, Reply to Supplemental Request for Additional Information for the Review of License Renewal Application (TAC No.ME4640) and License Renewal Application Amendment No. 33
L-12-274, Steam Generator Tube Circumferential Crack Report - Spring 2012 Refueling Outage
L-12-270, Withdrawal of License Amendment Request to Revise Emergency Diesel Generator Minimum Voltage Surveillance Requirements, and Add Figure Axis Labels
L-12-243, Reply to Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station, Unit No. 1, License Renewal Application (TAC No. ME4640) and License Renewal Application Amendment No. 28
L-12-254, Response to Regulatory Issue Summary 2012-07, Preparation and Scheduling of Operator Licensing Examinations
L-12-194, Report of Facility Changes, Tests, Experiments for Period Covering June 17, 2010 Through June 14, 2012
L-12-217, Reply to Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station, Unit No. 1, License Renewal Application
L-12-213, Core Operating Limits Report, Cycle 18
L-12-211, Completion of Actions Required by Confirmatory Action Letter 3-11-001
L-12-185, Supplemental Reply to Request for Additional Information for the Review of the License Renewal Application (TAC ME4640) and License Renewal Application Amendment No. 26
L-12-070, License Amendment Request to Revise Emergency Diesel Generator Minimum Voltage Surveillance Requirements, and Add Figure Axis Labels
L-12-166, Submittal of Annual Report of 10 CFR 50.46 of Changes to or Errors in ECCS Evaluation Models
L-12-138, CFR 50.55a Requests RP-2 and RP-4 Regarding Inservice Pump Testing
L-12-071, 10 CFR 50.46 Report of Significant Changes or Errors in the Loss of Coolant Accident Evaluation Model
L-12-065, Submittal of Shield Building Root Cause Evaluation
L-12-062, Response to a Request for Additional Information Regarding the Reactor Coolant System Pressure and Temperature Limits Report, Revision 1
L-12-055, Response to Request for Additional Information on 10 CFR 50.46 Report of Changes or Errors in ECCS Evaluation Models
L-12-021, Response to Request for Additional Information on License Amendment to Modify the Special Visual Inspection Requirements of Technical Specification 5.5.8, Steam Generator (Gs) Program (TAC ME6296.)
L-11-301, Ltr 11/7/2011 from FENOC to M. Satorius Davis-Besse Completion of Actions Required by Confirmatory Action Letter 3-10-001
L-11-376, Reply to Request for Supplemental Information for the Review of the License Renewal Application
L-11-359, Response to Request for Additional Information on 10 CFR 50-355a Request RR-A35, Proposed Alternative to System Leakage Test Requirements
L-11-354, Reply to Requests for Additional Information for the Review, License Renewal Application Amendment No. 22 & Revised License Renewal Application Boundary Drawings
L-11-353, Documentation of Commitments for the Davis-Besse Nuclear Power Station, Unit 1
L-11-343, Reply to Request for Additional Information for the Review of License Renewal Application
L-11-334, Reply to Request Additional Information for the Review of the License Renewal Application Amendment No. 21
L-11-319, Pressure and Temperature Limits Report
L-11-317, Reply to Request for Additional Information for the Review of License Renewal Application (TAC No. ME4640) and Amendment No. 20
L-11-292, Reply to Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station, Unit No. 1, License Renewal Application (TAC No. ME4640). License Renewal Application Amendment No. 19, and Revised License Renewal Applica
L-11-252, Reply to Request for Additional Information for the Review of License Renewal Application and License Renewal Application No. 15
L-11-251, Reply to Supplemental Request for Additional Information for Review of License Renewal Application, Environmental Report Severe Accident Mitigation Alternatives Analysis
L-11-218, Reply to Requests for Additional Information for the Review of the Davis-Besse Nuclear Power Station, Unit No. 1, License Renewal Application and License Renewal Application Amendment No. 12
L-11-203, Reply to Request for Additional Information for the Review of the License Renewal Application and License Renewal Application Amendment No. 9
L-11-166, Reply to Request for Additional Information for the Review of the License Renewal Application, Batch 3 (TAC No. ME4640), and License Renewal Application Amendment No. 8
L-11-156, Response to Request for Additional Information - 2010 Steam Generator Tube Inspection Report
L-11-167, CFR 50.46 Report of Changes or Errors in ECCS Evaluation Models, for the Period of January 1, 2010 to December 31, 2010
L-11-097, License Amendment Request to Modify the Special Visual Inspection Requirements of Technical Specification 5.5.8, Steam Generator (SG) Program
L-11-134, Reply to Request for Additional Information for the Review of License Renewal Application, Batch 1 and License Renewal Application Amendment No. 6
L-11-116, Pressure and Temperature Limits Report
L-11-115, Reply to Request for Additional Information for the Review of the License Renewal Application and License Renewal Application Amendment No. 4
L-11-091, CFR 50.55a Request RR-A35, Proposed Alternative to System Leakage Test Requirements
L-11-107, Reply to Request for Additional Information on Reactor Vessel Surveillance Aging Management Program & Time-Limited Aging Analyses for Neutron Embrittlement for Review of License Renewal Application & License Renewal Application.
L-11-120, Response to Request for Additional Information Regarding the Request for Approval of the Cyber Security Plan License Amendment Request
L-11-089, Reply to Request for Additional Information for the Review License Renewal Application
L-11-079, Reply to Request for Additional Information for the Review of the License Renewal Application
L-11-072, Response to Request for Additional Information Regarding Safety-Related Batteries Separation Design and Licensing Bases
L-11-078, Reply to Request for Additional Information for the Review of License Renewal Application (TAC ME4640) Amendment No. 1
L-11-037, Independent Spent Fuel Storage Installation - Changes, Tests, and Experiments
L-11-039, Response to Request for Additional Information Regarding the Request for Approval of the Cyber Security Plan License Amendment Request
L-10-314, Technical Specification 5.6.6 Steam Generator Tube Inspection Report
L-10-305, Response to Request for Additional Information Regarding 10 CFR 50.46 30-Day Report
L-10-326, Readiness for 95001 Supplemental Inspection; EA-09-283
L-10-263, Notification Letter Designating Davis-Besse Nuclear Power Station Balance of Plant Systems within the Cyber Security Rule Scope
L-10-271, Cycle 16 & Refueling Outage 16 Inservice Inspection Summary Report
L-10-265, Post-Outage Supplemental Response to Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems.
L-10-250, Notification of Significant Change to the Small-Break Loss-of-Coolant Accident Emergency Core Cooling Model in Accordance with 10 CFR 50.46(a)(3)
L-10-087, Response to Enforcement Action EA-09-332 from Davis-Besse Nuclear Power Station, Notice of Violation, Inspection Report No. 05000346-09-007
L-10-199, Response to Audit of Steam Generator Program Focusing on Steam Generator Tube Integrity During a Large-Break Loss-of-Coolant Accident
L-10-195, Request for Approval of Cyber Security Plan
L-10-205, Response to FOIA-2010-0209 Document Review Request
L-10-154, Report of Facility Changes, Tests, and Experiments
L-10-083, Core Operating Limits Report for Cycle 17
L-10-127, Submittal of Circumferential Cracking Report for Sixteenth Refueling Outage
L-10-133, Summary of Design and Analysis of Weld Overlays (Mode 4 Report)
L-10-178, Reactor Pressure Vessel Head Commitment Letter
L-10-166, Request for One-Time Exemption from the Requirements of 10 CFR 26.205(d)(3)
L-10-139, CFR 50.46 Report of Changes or Errors in ECCS Evaluation Models
L-10-111, Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pwrs.
L-10-131, Additional Information Regarding 10 CFR 50.55a Request RR-A34 for Alternative Repair Methods for Reactor Pressure Vessel Head Penetration Nozzles
L-10-123, Request for Additional Information Regarding 10 CFR 50.55a Request RR-A34 for Alternative Repair Methods for Reactor Pressure Vessel Head Penetration Nozzles
L-10-099, 10 CFR 50.55a Request for Alternate Repair Methods for Reactor Pressure Vessel Head Penetration Nozzles
L-10-088, Reply to a Notice of Violation: EA-09-283
L-10-043, Submittal of Annual Fitness-For-Duty Report, 2009
L-10-046, Withdrawal of a License Amendment Request to Exclude the Source Range Neutron Flux Instrument Channel Preamplifier from the TS Channel Calibration Requirements
L-10-044, Response to Specific Issues on Tube Integrity Analyses Performed for the Large Break Loss-of-Coolant Accident
L-10-037, Response to Preliminary White Finding in Inspection Report 2009-503 (EA-09-283)
L-09-335, Request for Extension of Enforcement Discretion for Noncompliances Related to Fire Protection Programs
L-09-225, Supplemental Information Related to a License Amendment Request to Incorporate the Use of Alternate Methodologies for the Development of Reactor Pressure Vessel Pressure-Temperature Limit Curves, and Request for Exemption from
L-09-319, Request to Withhold from Public Disclosustructural Integrity Associates, Inc. Report Number 0800368.404, Revision 0, July 20, 2009
L-09-263, Response to NRC Request for Additional Information Regarding Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems.
L-09-227, License Amendment Request to Update the Leak-Before-Break Evaluation for the Reactor Coolant Pump Suction and Discharge Nozzle Dissimilar Metal Welds
L-09-215, Response to Individual Plant Actions Pressurized-Water Reactor Owners Group Topical Report BAW-2374, Rev. 2,Risk-Informed Assessment of Once-Through Steam Generator Tube Thermal Loads Due to Breaks in Reactor Coolant System
L-09-190, Renewal of Quality Assurance Program Approval 0195
L-09-179, Response to Requests for Additional Information Related to Alternative Dissimilar Metal Weld Repair Methods
L-09-033, FENOC, EA-03-214, Completion of Actions Required by Confirmatory Order for Davis-Besse Power Station
L-09-125, Submittal of Annual Report of Changes to the Emergency Core Cooling System Evaluation Model and in the Application of the Model in Accordance with 10 CFR 50.46(a)(3)
L-09-130, Response to Request for Additional Information the 2008 Steam Generator Tube Inspections
L-09-072, License Amendment Request to Incorporate the Use of Alternate Methodologies for Development of Reactor Pressure Vessel Pressure-Temperature Limit Curves and Request for Exemption from Certain Requirements Contained in 10 Cfr
L-08-219, Submittal of 2008 Confirmatory Order Independent Assessment Report of Operations Performance
L-09-068, Independent Spent Fuel Storage Installation - 10 CFR 72.48 Report of Dry Fuel Storage Facility Changes, Tests, and Experiments
L-09-039, Semiannual Fitness-For-Duty Report, July - December 2008
L-09-020, 10 CFR 50.55a Requests for Alternative Dissimilar Metal Weld Repair Methods for Reactor Vessel Nozzles, Reactor Coolant Pump Nozzles, and Reactor Coolant Piping
L-09-011, First Energy Nuclear Operating Company - Davis Besse, 2008 Independent Assessment of the Davis-Besse Nuclear Power Station Safety Culture and Safety Conscious Work Environment Report
L-08-317, Core Operating Limits, and Pressure and Temperature Limits Report
L-08-354, Relocation of Relief Request RR-A18, Snubber Examination and Test Requirements
L-08-378, Implementation of Improved Technical Specification Amendment No. 279
L-08-382, Regulatory Conference Comment Clarification
L-08-357, Submittal of 2008 Confirmatory Order Independent Assessment Report of Engineering Programs Effectiveness
L-08-338, Copy of Improved Technical Specifications (ITS)
L-08-314, Nine Month Response to NRC Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems.
L-08-251, 2008 Independent Corrective Action Program Assessment Report, March 2004 Confirmatory Order
L-08-224, Response to Request for Additional Information License Amendment Request to Convert Current Technical Specifications (CTS) to Improved Technical Specifications (Its), and Copy of Two Questions from NRC and Davis-Besse Its
L-08-248, Submittal of Semiannual Fitness-For-Duty Report, January - June 2008
L-08-256, Response to Request for Additional Information Regarding Bulletin 2007-01, Security Officer Attentiveness
L-08-152, Submittal of Technical Specification 6.9.1.12 Steam Generator Tube Inspection Report for January 2008 15th Refueling Outage
L-08-221, Response to Request for Additional Information Related to Improved Technical Specifications Conversion
L-08-233, Response to Request for Additional Information Regarding Summary of Design and Analyses of Weld Overlays for Pressurizer and Hot Leg Nozzle Large Bore Dissimilar Metal Welds
L-08-228, Core Operating Limits Report, Revision 1, Supports the Implementation of License Amendment 278, Measurement Uncertainty Recapture (MUR) Power Uprate
L-08-194, First Energy Nuclear Operating Company Submittal of Engineering Program Effectiveness Assessment Plan for the Davis-Besse Nuclear Power Station - Year 2008
L-08-139, Submittal of Report of Facility Changes, Tests and Experiments for Period of May 19, 2006 Through February 14, 2008
L-08-167, Transmittal of Technical Specification Bases Update
L-08-193, Firstenergy Nuclear Operating Company - Davis Besse Letter to J. Caldwell Re Submittal of Organization Safety Culture and Safety Conscious Work Environment Independent Assessment Plan
L-08-168, Report of Changes to the Emergency Core Cooling System Evaluation Model in Accordance with 10 CFR 50.46(a)(3)
L-08-159, Supplement to License Amendment Request: Conversion of Current Technical Specifications (CTS) to Improved Technical Specifications (ITS) - Volumes 5, 6, 7, 9, 11, and 15, TAC No. MD6398
L-08-161, Copy of Applicable Portions of the NRC and Davis-Besse Improved Technical Specifications Conversion Website - Sections 3.0, 3.1, 3.2, 3.4, and 3.6 and Chapter 4.0
L-08-175, Response to Request for Additional Information and Supplemental Information Regarding Application for License Amendment for Measurement Uncertainty Recapture Power Uprate
L-08-136, Cycle 15 and Refueling Outage 15 Inservice Inspection Summary Report
L-08-105, Reactor Head Inspection Report
L-08-104, Steam Generator Tube Circumferential Cracking Report for the Fifteenth Refueling Outage
L-08-132, Three Month Response to NRC Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems
L-08-110, Corrective Action Program Assessment Plan for 2008
L-08-080, Response to Confirmatory Action Letter No. NRR-07-017
L-08-059, Semiannual Fitness-For-Duty Report for Time Period of July 1, 2007 Through December 31, 2007
L-08-066, Inservice Inspection Program Relief Requests IR-043, Revision 1, IR-055, IR-056, and IR-057
L-08-046, Request to Adopt TSTF-476-A, Improved BPWS Control Rod Insertion Process (NEDO-33091), Per the Consolidated Line Item Improvement Process
L-08-038, Transmittal of Annual Report for the 2007
L-08-051, Transmittal of Response to Bulletin 2007-01, Security Officer Attentiveness
W3F1-2002-0012, Revision to Peak Linear Heat Rate Safety Limit Technical Specification 2.1.1.2
W3F1-2002-0006, Response to Requests for Additional Information on Technical Specification Change Request, NPF-38-238 Regarding Appendix K Margin Recovery, Power Uprate Request
DCL-15-135, Response to NRC Request for Additional Information Regarding License Amendment Request 15-03, Application of Alternative Source Term
DCL-15-116, Submittal of 10 CFR 50.55a Request FLIG-U1, Request for Extension of Third Inservice Inspection Interval for Performing Reactor Vessel Stud Hole Ligament Examinations
DCL-15-115, Withdrawal of License Amendment Request 15-04, Exigent Revision to Technical Specification 3.8.9. Distribution Systems- Operating
DCL-15-107, License Amendment Request 15-07, Revision of Reactor Coolant System Minimum Flow Specified in Technical Specification 3.4.1. RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits
DCL-15-105, Supplement to License Amendment Request 15-03, Application of Alternative Source Term
DCL-15-098, Pacific Gas and Electric Companys Fifth Six-Month Status Report in Response to March 12. 2012, Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)
DCL-15-102, 10 CFR 71.95 Report Regarding Energy Solutions Model 8-120B Shipping Cask
DCL-15-065, Response to NRC Request for Additional Information Regarding License Amendment Request 13-02. Revision to Technical Specifications to Adopt Risk Informed Completion Times TSTF-505. Revision 1. Provide Risk-Informed
DCL-15-055, Response to NRC Request for Additional Information Regarding License Amendment Request 14-03, License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-432, Rev 1, Change in Technical.
DCL-15-052, Response to NRC Request for Additional Information Regarding License Amendment Request 14-01, Revision to Technical Specification 3.8.1, AC Sources - Operating
DCL-15-047, License Amendment Request 15-02 Revision of Updated Final Safety Analysis Report for Beacon Power Distribution Monitoring System Methodology and Technical Specification 5.6.5. Core Operating Limits Report (Colr), For.
05000275/LER-2014-003-02, Regarding Unanalyzed Condition Affecting Emergency Diesel Generators, Tornado Missiles
DCL-14-111, American Society of Mechanical Engineers Section Xl Inservice Inspection Program Relief Request NDE-RCS-SE-2R19 - Use of Alternate Sizing Qualification Criteria Through a Protective Clad Layer
05000275/LER-2014-004, Actuation of Six Emergency Diesel Generators Due to Loss of Offsite Power
DCL-14-086, Relief Request SWOL-REP-1 U2: Submittal of Westinghouse Letter, LTR-RC-14-45, Proprietary Information Clarification Request Response
DCL-14-078, Request for Enforcement Discretion Regarding Compliance with Technical Specification 3.8.1, AC Sources - Operating
05000275/LER-2014-003-01, Regarding Unanalyzed Condition Affecting Unit 1 and 2 Emergency Diesel Generators, Tornado Missiles
05000275/LER-2013-009-01, Regarding Unanalyzed Condition Affecting Unit 1 Emergency Diesel Generators
05000275/LER-2014-003, Regarding Unanalyzed Condition Affecting Unit 1 and 2 Emergency Diesel Generators, Tornado Missiles
05000323/LER-2014-001, Regarding Lightning Arrester Failure Resulting in Reactor Trip
05000275/LER-2014-001, Regarding Technical Specification 3.4.3, Reactor Coolant System Pressure Limit Violation During Vacuum Refill Due to Human Error
DCL-14-014, Pacific Gas and Electric Companys Second Six-Month Status Report in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order EA-12
05000275/LER-2013-010, Regarding Two Emergency Diesel Generators Inoperable Due to Operator Error
05000275/LER-2013-009, Regarding Unanalyzed Condition Affecting Unit 1 Emergency Diesel Generators
05000275/LER-2013-006-01, Regarding Emergency Diesel Generators Valid Start Signal Due to Loss of Startup Power
05000275/LER-2013-008, Regarding Technical Specification 3.3.4 Not Met Due to Inoperable Remote Shutdown System Function
DCL-13-117, Re Auxiliary Feedwater Actuation Due to Main Feedwater Pump Trip
05000275/LER-2013-003-01, Regarding Actuation of Six Emergency Diesel Generators Due to Loss of Offsite Power
05000275/LER-2013-006, Regarding Emergency Diesel Generators Valid Start Signal Due to Loss of Startup Power
05000323/LER-2013-005, Regarding Unit 2 Reactor Trip Due to Lightning Arrester Flashover
05000275/LER-2013-004, Regarding All Three Unit 1 Emergency Diesel Generators Momentarily Inoperable
05000275/LER-2013-003, Regarding Actuation of Six Emergency Diesel Generators Due to Loss of Offsite Power
05000275/LER-2013-005, Both Trains of Residual Heat Removal Inoperable Due to Circumferential Crack on a Socket Weld
DCL-13-080, Pacific Gas and Electric Companys First Six-Month Status Report in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)
05000323/LER-2013-004, Regarding Technical Specification 3.8.1 Not Met Due to Failed Wire Lug on Emergency Diesel Generator 2-3
05000275/LER-2012-005-01, Regarding Unanalyzed Condition Due to Nonconservative Change in Atmospheric Dispersion Factor
05000323/LER-2013-002, Both Source Range Nuclear Instruments Inoperable While in Mode 6
DCL-13-046, Response to NRC Request for Additional Information Regarding Request for Approval of an Alternative to the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Section XI Pressure Test.
DCL-13-043, Supplement to License Amendment Request 11-07. Process Protection System Replacement
05000323/LER-2013-001, Regarding Valid EDG 2-1 Start Signal Caused by a Loss of 4KV Class 1E Bus G
05000275/LER-2013-001, Noncompliance with TS 3.4.12, Low Temperature Overpressure Protection System Due to Human Error
05000275/LER-2012-007-01, Inadequately Compensated Non-Conformances in the Fire Protection Program
05000275/LER-2012-008, Regarding Loss of Control Room Ventilation System Due to Inadequate Design Control
05000275/LER-2011-008-01, Control Room Ventilation System Design Vulnerability
05000275/LER-2011-007-02, Inadequate Control Room Envelope Testing Due to Inadequately-Documented In-leakage Test Data
05000275/LER-2012-007, Regarding Inadequately Compensated Non-Conformances in the Fire Protection Program
05000323/LER-2012-002, Regarding Coupling Capacitor Voltage Transformer Bushing Failure Causes Reactor Trip
DCL-12-122, License Amendment Request 12-04, Emergency Revision to Technical Specification 3.7.10, Control Room Ventilation System (Crvs)
DCL-12-107, Supplement to PG&E Letter DCL-11-059, License Amendment Request 11-04, Revision to Technical Specification (TS) 3.6.6, Containment Spray and Cooling Systems, TS 3.7.5, Auxiliary Feedwater (AFW) System, TS 3.8.1, Ac...
05000323/LER-2012-001, Regarding Failure to Meet Emergency Diesel Generator Technical Specifications
05000275/LER-2012-006, Regarding Violation of Technical Specifications Due to Incorrect Bases
05000346/LER-2012-002, Regarding Leak from Reactor Coolant Pump Seal Piping Socket Weld Due to High Cycle Fatigue
05000346/LER-2012-001, For Davis-Besse Regarding Direct Current Source for Diesel Generator Transferred to Inoperable Source During Fuel Movement
05000346/LER-2011-004, Regarding Direct Current System Design Issues
05000346/LER-2011-003, Regarding Radio Usage Renders Emergency Feedwater Inoperable
05000346/LER-2011-002, Regarding Containment Air Cooler Isolation Valve Disabled Due to Drawing Omission
05000346/LER-2011-001, For Davis-Besse Nuclear Power Station, Regarding Pressurizer Code Safety Valve Setpoint Test Failures
05000346/LER-2010-004, Re Spent Fuel Pool Rack Patterns Did Not Comply with Technical Specification 3.7.16
05000346/LER-2010-003, Auxiliary Feedwater Control Valve Inoperable Due to Inadequate Prioritization of DC System Ground
L-10-243, Response to a Request for Additional Information Related to a License Amendment Request to Incorporate the Use of Alternative Methodologies for the Development of RPV P-T Curves, and Request for Exemption from Certain Requirements
L-10-213, Response to Regulatory Issue Summary 2010-08, Preparation and Scheduling of Operator Licensing Examinations
05000346/LER-2010-002, Regarding Control Rod Drive Nozzle Primary Water Stress Corrosion Cracking and Pressure Boundary Leakage
05000346/LER-2010-001, Regarding Steam and Feedwater Rupture Control System Re-Energizes in a Blocked Condition on Loss of Offsite Power
05000346/LER-2009-002, Regarding Vibration Induced Failure of Temperature Instrument Results in Operation Above Licensed Power Limit
05000346/LER-2009-001, Regarding Containment Air Cooler Fans Inoperable Due to Misapplication of Potter and Brumfield Rotary Relays
L-09-219, Response to Regulatory Issue Summary 2009-11, Preparation and Scheduling of Operator Licensing Examinations
L-09-143, License Amendment Request to Exclude Source Range Neutron Flux Instrument Channel Preamplifier from Channel Calibration Requirements of Technical Specification 3.3.9, Source Range Neutron Flux, & TS 3.9.2, Nuclear Instrumentation
05000440/LER-2008-001, Regarding Condition Prohibited by Technical Specifications Due to Unrecognized Reactor Core Isolation Cooling Inoperability
05000440/LER-2007-006, Regarding Loss of Safety Function and Condition Prohibited by Technical Specifications Due to Annulus Exhaust Gas Treatment System Inoperability
05000440/LER-2007-005, Regarding Plant Startup with Inoperable Reactor Core Isolation Cooling System
05000440/LER-2007-004-01, 1 for Perry Nuclear Power Plant Re Automatic Reactor Protection System Actuation Due to Feedwater Control Power Supply Failure
05000440/LER-2007-004, Automatic Reactor Protection System Actuation Due to Feedwater Control Power Supply Failure
05000440/LER-2007-002, For Perry, Shutdown Cooling Pump Trip Results in Operation Prohibited by Technical Specifications
05000440/LER-2007-001, From Perry Regarding Automatic Reactor Protection System Actuation Due to Reactor Coolant Level Decrease
L-11-307, Ltr 10/19/11 Davis-Besse Re Experience Requirement Waiver Request for Licensed Operator Applicant